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| number = ML16207A548
| number = ML16207A548
| issue date = 04/28/2016
| issue date = 04/28/2016
| title = South Texas, Units 1 and 2, Revision 18 to Updated Safety Analysis Report, Chapter 6, Table of Contents
| title = Revision 18 to Updated Safety Analysis Report, Chapter 6, Table of Contents
| author name =  
| author name =  
| author affiliation = South Texas Project Nuclear Operating Co
| author affiliation = South Texas Project Nuclear Operating Co

Revision as of 03:19, 2 February 2019

Revision 18 to Updated Safety Analysis Report, Chapter 6, Table of Contents
ML16207A548
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STPEGS UFSAR T C 6-1 Revision 1 8 TABLE OF CONTENTS CHAPTER 6 ENGINEERED SAFETY FEATURES

Section Title Page 6.1 ENGINEERED SAFETY FEATURES MATERIALS 6.1-1 6.1.1 Metallic Materials 6.1-1 6.1.2 Organic Materials 6.1-3 6.1.3 Post Accident Chemistry 6.1-5 6.1.4 Post Accident Sump Solution Chemistry Adjustment 6.1-5 6.2 CONTAINMENT SYSTEMS 6.2-1 6.2.1 Containment Functional Design 6.2-1 6.2.2 Containment Heat Removal Systems 6.2-29 6.2.3 Secondary Containment Functional Design (Does not apply to STPEGS) 6.2-4 0 6.2.4 Containment Isolation System 6.2-4 0 6.2.5 Combustible Gas Control in Containment 6.2-4 7 6.2.6 Containment Leakage Testing 6.2-49 6.3 EMERGENCY CORE COOLING SYSTEM 6.3-l 6.3.l Design Bases 6.3-l 6.3.2 System Design 6.3-2 6.3.3 Performance Evaluation 6.3-17 6.3.4 Tests and Inspections 6.3-25 6.3.5 Instrumentation Requirements 6.3-27 6.4 HABITABILITY SYSTEMS 6.4-l 6.4.l Design Bases 6.4-l 6.4.2 System Design 6.4-2 6.4.3 System Operational Procedures 6.4-5 6.4.4 Design Evaluation 6.4-5 6.4.5 Testing and Inspection 6.4-7 6.4.6 Instrumentation Requirement 6.4-9 6.5 FISSION PRODUCT REMOVAL AND CONTROL SYSTEMS 6.5-l 6.5.l Engineered Safety Feature Filter Systems 6.5-l 6.5.2 Containment Spray System

- Iodine Removal 6.5-4 6.5.3 Fission Product Control Systems 6.5-8 STPEGS UFSAR TABLE OF CONTENTS (Continued)

CHAPTER 6 Section Title Page T C 6-2 Revision 1 8 6.6 INSERVICE INSPECTION OF ASME CODE CLASS 2 AND CLASS 3 COMPONENTS 6.6-l 6.6.l Components Subject to Inspection 6.6-l 6.6.2 Accessibility 6.6-l 6.6.3 Examination Techniques and Procedures 6.6-2 6.6.4 Inspection Intervals 6.6-2 6.6.5 Examination Categories and Requirements 6.6-2 6.6.6 Evaluation of Examination Results 6.6-2 6.6.7 System Pressure Tests 6.6-3 6.6.8 Augmented Inservice Inspection 6.6-3 6.7 MAIN STEAM ISOLATION VALVE LEAKAGE CONTROL 6.7-1 SYSTEM TC 6-3 Revision 1 8 LIST OF TABLES CHAPTER 6 Table Title Page 6.1-1 Engineered Safety Features Materials 6.1-7 6.1-3 Protective Coatings on Westinghouse

-Supplied Equipment Inside Containment 6.1-1 1 6.1-4 Coating Schedule for Surfaces Inside Containment (Excluding NSSS Scope of Supply) 6.1-12 6.2.1.1-1 Containment Design Accidents 6.2-56 6.2.1.1-2 DBA Calculated Pressures in Containment 6.2-58 6.2.1.1-3 Containment Data Used in P/T Analysis 6.2-59 6.2.1.1-4 Not Used 6.2.1.1-5 Engineered Safety Features System Information 6.2-6 1 6.2.1.1-7 Modeling of Structural Heat Sinks for Containment Analyses 6.2-6 2 6.2.1.1-8 Thermophysical Properties of Structural Heat Sink Materials for Containment Analysis 6.2-6 5 6.2.1.1-9 Containment Heat Sink Surface Heat Transfer Model 6.2-6 6 6.2.1.1-10 Accident Chronology for DBA LOCA 6.2-6 7 6.2.1.1-14 Summary of Containment MSLB P/T Analysis Results 6.2-6 8 6.2.1.1-15 Accident Chronology for DBA MSLB (Peak Temperature Case) 6.2-7 0 6.2.1.2-1 (Item G)

Short-Term Mass and Energy Release Rates for Subcompartment Analyses for Pressurizer Spray Line DEG Break 6.2-7 2 6.2.1.2-1 (Item J)

Short-Term Mass and Energy Release Rates for Subcompartment Analyses for MSLB 6.2-8 2 6.2.1.2-1 (Item K)

Short-Term Mass and Energy Release Rates for Subcompartment Analyses for Main Feedwater Line Break 6.2-8 3 6.2.1.2-1 (Item L)

Short-Term Mass and Energy Release Rates for Subcompartment Analyses for CVCS Letdown Line Break

- Radioactive Pipe 6.2-8 5 Chase Subcompartment Blowdown 6.2.1.2-1 (Item M)

Short-Term Mass and Energy Release Rates for Subcompartment Analyses for CVCS Letdown Line Break

- RHR 1A Valve Room Subcompartment Analyses 6.2-8 6 6.2.1.2-1 (Item N)

Short-Term Mass and Energy Release Rates for Subcompartment Analyses for CVCS Letdown Line Break

- Regenerative Heat Exchanger Subcompartment Blowdown 6.2-88 6.2.1.2-1 (Item P)

Short-Term Mass and Energy Release Rates for Subcompartment Analysis for RHR 12" Line DEG 6.2-89 6.2.1.2-1 (Item Q)

Short-Term Mass and Energy Release Rates for Subcompartment Analysis for FW 16" DEG Break at SG Nozzle Connection, HFP, FW @ 460 F 6.2-97 LIST OF TABLES (Continued)

CHAPTER 6 Table Title Page TC 6-4 Revision 1 8 6.2.1.2-5A Steam Generator Loop Compartment Peak Pressure Summary for RHR Line Break Analysis 6.2-94 6.2.1.2-5B Steam Generator Loop Compartment Peak Pressure Summary for FWLB Analysis 6.2-96 6.2.1.2-6 Steam Generator Loop Compartment Pressure

- Junction Properties for RHR/SI Analysis (42

-Node Model) 6.2-98 6.2.1.2-6A Steam Generator Loop Compartment Pressure Analysis

- Junction Properties for FWLB Analysis 6.2-102 6.2.1.2-7A Steam Generator Loop Compartment Analysis

- Force Coefficient (Area Projections) for Steam Generator Subjected to RHR Line Break 6.2-104 6.2.1.2-7B Steam Generator Loop Compartment Analysis

- Moment Coefficient (Area Projections) for Steam Generator Subjected to RHR Line Break 6.2-105 6.2.1.2-7C Steam Generator Loop Compartment Analysis

- Force Coefficient (Area Projections) for Steam Generator Subjected to FWLB 6.2-106 6.2.1.2-7D Steam Generator Loop Compartment Analysis

- Moment Coefficient (Area Projections) for Steam Generator Subjected to FWLB 6.2-107 6.2.1.2-8A Steam Generator Loop Compartment Analysis

- Force Coefficient (Area Projections) for Reactor Coolant Pump Subjected to RHR Line Break 6.2-1 08 6.2.1.2-8B Steam Generator Loop Compartment Analysis

- Moment Coefficient (Area Projections) for Reactor Coolant Pump Subjected to RHR Line Break 6.2-109 6.2.1.2-9 Pressurizer Subcompartment Analysis Spray Line Break 6.2-110 6.2.1.2-13 Main Steam Line and Feedwater Line Subcompartment Analysis 6.2-111 6.2.1.2-14 Main Steam Line and Feedwater Subcompartment Analysis Junction Description

- Steam Line Break Analysis 6.2-112 6.2.1.2-15 Regenerative Heat Exchanger Subcompartment Nodal Description 6.2-113 STPEGS UFSAR LIST OF TABLES (Continued)

CHAPTER 6 Table Title Page TC 6-5 Revision 1 8 6.2.1.2-16 Regenerative Heat Exchanger Subcompartment Junction Description 6.2-114 6.2.1.2-17 Radioactive Pipe Chase Subcompartment Nodal Description 6.2-115 6.2.1.2-18 Radioactive Pipe Chase Subcompartment Junction Description 6.2-116 6.2.1.2-19 RHR1A Valve Room Subcompartment Nodal Description 6.2-117 6.2.1.2-20 RHR1A Valve Room Subcompartment Junction Description 6.2-118 6.2.1.3-1 System Parameter Initial Conditions 6.2-119 6.2.1.3-2 LOCA - Total Pumped ECCS Flow Rate for Two Trains of SI Operating 6.2-120 6.2.1.3-3 LOCA - Total Pumped ECCS Flow Rate for Three Trains of SI Operating 6.2-121 6.2.1.3-4 Double-Ended Hot Let Break Blowdown Mass and Energy Releases 6.2-122 6.2.1.3-5A Double-Ended Pump Suction Break Mass and Energy Releases (Minimum SI) 6.2-125 6.2.1.3-5B Double-Ended Pump Suction Break Mass and Energy Releases (Maximum SI) 6.2-132 6.2.1.3-6 Decay Heat Data Based on ANS

-51.1-1979 Plus 2 Sigma Uncertainty 6.2-141 6.2.1.3-6A Decay Heat Based on Standard Review Plan ASB 9

-2 Correlations 6.2-142 6.2.1.3-7 Not Used 6.2.1.3-8 Not Used 6.2.1.3-9 Double-Ended Pump Suction Break Principal Parameters During Reflood (Minimum SI) 6.2-144 6.2.1.3-10 Double-Ended Pump Suction Break Principal Parameters During Reflood (Maximum SI) 6.2-145 6.2.1.3-11 Not Used 6.2.1.3-12 Not Used 6.2.1.3-13 Double-Ended Pump Suction Break Mass Balance (Minimum SI) 6.2-146 6.2.1.3-14 Double-Ended Pump Suction Break Mass Balance (Maximum SI) 6.2-147 6.2.1.3-15 Double-Ended Hot Let Break Mass Balance 6.2-148 6.2.1.3-16 Double-Ended Pump Suction Break Energy Balance (Minimum SI) 6.2-149 6.2.1.3-17 Double-Ended Pump Suction Break Energy Balance (Maximum SI) 6.2-150 6.2.1.3-18 Double-Ended Hot Leg Break Energy Balance 6.2-151 6.2.1.4-l Mass and Energy Release Rates for Main Steam Line Break - 1.4 ft 2 Double-Ended Rupture at 30% Power (MSIV Failure) 6.2-152 STPEGS UFSAR LIST OF TABLES (Continued)

CHAPTER 6 Table Title Page TC 6-6 Revision 1 8 6.2.1.4-2 Mass and Energy Release Rates for Main Steam Line Break - 1.4 ft 2 Double-Ended Rupture at 0% Power (MSIV Failure) 6.2-1 56 6.2.1.5-1 Blowdown Mass and Energy Releases 6.2-160 6.2.1.5-1a Broken Loop Injection Spill During Blowdown 6.2-161 6.2.1.5-2 Reflood Mass and Energy Releases 6.2-162 6.2.1.5-3 Active Heat Sink Data for Minimum Post LOCA Containment Pressure 6.2-163 6.2.1.5-4 Passive Heat Sink Data for Minimum Post LOCA Containment Pressure 6.2-164 6.2.2-1 Containment Spray System

- Design Parameters 6.2-166 6.2.2-2 Design Data for the Reactor Containment Fan Cooler (RCFC) System 6.2-167 6.2.2-3 Failure Modes and Effect Analysis

- Containment Heat Removal Active Failure 6.2-170 6.2.2-4 CSS Pump NPSH Parameters 6.2-1 74 6.2.2-5 Estimate of CSS Spray Mass Flow Rates for Various Regions 6.2-1 75 6.2.4-1 Containment Isolation System Failure Modes and Effect Analysis 6.2-1 76 6.2.6-1 Systems Which Need not be Vented During Type A Testing 6.2-1 84 6.2.6-3 Containment Isolation Valves to be Leak Tested in Opposite Direction 6.2-1 86 6.3-1 Emergency Core Cooling System Component Parameters 6.3-32 6.3-2 ECCS Relief Valve Data 6.3-34 6.3-3 Motor-Operated Valves in ECCS 6.3-35 6.3-4 Materials Employed for Emergency Core Cooling System Components 6.3-37 6.3-5 Single Active Failure Analysis for Emergency Core Cooling System Components Short Term Phase 6.3-39 6.3-6 Emergency Core Cooling System Recirculation Piping - Passive Failure Analysis, Long

-Term Phase 6.3-40 6.3-7 Manual Actions Required for Safety Injection Modes of Operation 6.3-41 6.3-8 Emergency Core Cooling System Shared Functions Evaluation 6.3-42 6.3-10 Emergency Core Cooling System

- Safeguards Operations Failure Modes and Effects Analysis 6.3-43 STPEGS UFSAR LIST OF TABLES (Continued)

CHAPTER 6 Table Title Page TC 6-7 Revision 1 8 6.3-11 ECCS Check Valves to be Leak Tested 6.3-48 6.3-12 ECCS Active Powered Components 6.3-49 6.3-13 Air-Operated Valves in the ECCS 6.3-51 6.3-14 Solenoid-Operated Valves in the ECCS 6.3-52 6.4-1 Equipment to Which the Control Room Operators Could Require Access During an Emergency 6.4-11 6.4-2 Control Room Dose Analysis 6.4-12 6.5-1 Comparison of Engineered Safety Feature Filter Systems with Regulatory Guide l.52, Rev. 2, Requirements 6.5-11 6.5-2 Input Parameters for Determining Iodine Removal Coefficients 6.5.14 6.5-3 Input Parameters to Determine Minimum pH for Sump Solution 6.5-15 6.5-4 Input Parameters to Determine Maximum pH for Sump Solution 6.5-16 STPEGS UFSAR LIST OF FIGURES (Continued

)

CHAPTER 6 Figure Reference Number Title Number TC 6-8 Revision 1 8 6.2.1.1-3 Not used 6.2.1.1-25 Containment Pressure

- 1.4 ft 2 Double-Ended MSLB (0% Power, MSIV Failure) 6.2.1.1-26 Not Used 6.2.1.1-27 Containment Temperature

- 1.4 ft 2 Double-Ended MSLB (0% Power, MSIV Failure) 6.2.1.1-28 Condensing Heat Transfer Coefficient

- 1.4 ft 2 Double-Ended MSLB (0% Power, MSIV Failure) 6.2.1.1-29 Total Vapor Region Energy - 1.4 ft 2 Double-Ended MSL B (0% Power, MSIV Failure) 6.2.1.1-30 Containment Pressure

- LOCA DEHL 6.2.1.1-31 Containment Temperatures

- LOCA DEHL 6.2.1.1-32 Heat Transfer Coefficient

- LOCA DEHL 6.2.1.1-33 Containment Pressure

-LOCA DEPS (Minimum SI) 6.2.1.1-34 Containment Temperatures

- LOCA DEPS (Minimum SI) 6.2.1.1-35 Heat Transfer Coefficient

- LOCA DEPS (Minimum SI) 6.2.1.1-36 Containment Pressure

- LOCA DEPS (Maximum SI) 6.2.1.1-37 Containment Temperatures

- LOCA DEPS (Maximum SI) 6.2.1.1-38 Heat Transfer Coefficient

- LOCA DEPS (Maximum SI)

STPEGS UFSAR LIST OF FIGURES (Continued

)

CHAPTER 6 Figure Reference Number Title Number TC 6-9 Revision 1 8

  • The drawings below are reference drawings only and are not to be revised.

6.2.1.2-3 Steam Generator Loop Compartment Node Arrangement El. (-)11'33" - (Sheet 1 of 8) 6C18-9-N-05001-2* El. (-)2'-0" - (Sheet 2 of 8) 6C18-9-N-05002-2* El. 19'0-" - (Sheet 3 of 8) 6C18-9-N-05003-2* El. (-)37'3" - (Sheet 4 of 8) 6C18-9-N-05004-2* El. 52'0" - (Sheet 5 of 8) 6C18-9-N-05005-1* El. 68'0" - (Sheet 6 of 8) 6C18-9-N-05006-2* Section AA - (Sheet 7 of 8) 6C18-9-N-05007-3* Section BB

- (Sheet 8 of 8) 6C18-9-N-05008-2* 6.2.1.2-4 Pressurizer Compartment Nodes Between:

El. 69'-9" & 85'-0" - (Sheet 1 of 3) 6C18-9-N-05006-4* El. 46'-7" & 69'-9" - (Sheet 2 of 3) 6C18-9-N-0500 5-2* (Sheet 3 of 3) 6C18-9-N-05008-4* 6.2.1.2-5 Surge Line Subcompartment Nodes Between:

El. 46'-4" & 69'-9" - (Sheet 1 of 5) 6C18-9-N-05005-2* El. 37'-3" & 43'-4" - (Sheet 2 of 5) 6C18-9-N-05004-3* El. 19'-0" & 37'-3" - (Sheet 3 of 5) 6C18-9-N-05003-3* El. 5'-9" & 19'-0" - (Sheet 4 of 5) 6C18-9-N-05002-3* (Sheet 5 of 5) 6C18-9-N-05008-2* 6.2.1.2-6 Main Steamline and Feedwater Line Subcompartment Nodes Between:

El. 19'-0" & 37'-3" - (Sheet 1 of 3) 6C18-9-N-05003-3* El. 37'-3" & 52'-0" - (Sheet 2 of 3) 6C18-9-N-05004-3* El. 52'-0" & 68'-0" - (Sheet 3 of 3) 6C18-9-N-05005-2* 6.2.1.2-7 Regenerative Heat Exchanger Subcompartment Nodes Between El. 37'-3" & 52'-0" 6C18-9-N-05004-4* 6.2.1.2-8 Radioactive Pipe Chase Between Elevations 29' & 37'

-3" 5C15-9-P-05029-1* 6.2.1.2-9 RHR 1A and 1B Valve Room Subcompartment

STPEGS UFSAR LIST OF FIGURES (Continued

)

CHAPTER 6 Figure Reference Number Title Number TC 6-10 Revision 1 8 Nodes Between:

El. 37'3" and 52'0" - (Sheet 1 of 2) 6C18-9-N-05004-4* (Sheet 2 of 2) 6C18-9-N-05003-4* 6.2.1.2-11 Node and Junction Diagram for Steam Loop Compartment (4 Sheets) 6.2.1.2-11A Nodalization Diagram for Steam Generator Loop Compartment for FWLB Analysis (8 sheets) 6.2.1.2-12 Pressurizer Subcompartment Nodal Model 6.2.1.2-13 Surge Line Subcompartment Nodal Model 6.2.1.2-14 Main Steam and Feedwater Line Subcompartment Nodal Model 6.2.1.2-15 Regenerative Heat Exchanger Subcompartment Nodal Model 6.2.1.2-16 Radioactive Pipe Chase Subcompartment Nodal Model 6.2.1.2-17 RHR Valve Room Subcompartment Nodal Model 6.2.1.2-20A Steam Generator Loop Compartment Pressurization Analysis, 12" RHR Break in Node 15 (11 sheets) 6.2.1.2-20B Steam Generator Loop Compartment Pressurization Analysis, 12" RHR Break in Node 4 (11 sheets) 6.2.1.2-20C Steam Generator Loop Compartment Pressurization Analysis, 12" RHR Break in Node 12 (11 sheets) 6.2.1.2-20D Steam Generator Loop Compartment

STPEGS UFSAR LIST OF FIGURES (Continued

)

CHAPTER 6 Figure Reference Number Title Number TC 6-11 Revision 1 8 Pressurization Analysis, 16" FWLB (Nodes 1& 17) 6.2.1.2-21A Steam Generator Forces and Moments Analysis

- Steam Generator Forces due to RHR Break in Nodes 15 (6 sheets) 6.2.1.2-21B Steam Generator Loop Compartment Forces and Moments on Steam Generator due to FWLB (11 sheets) 6.2.1.2-22A Reactor Coolant Pump Forces and Moments due to RHR Break in Node 15 (6 sheets) 6.2.1.2-23 Pressurizer P

-T Analysis (3 Sheets) 6.2.1.2-25 MSLB Subcompartment P

-T Analysis (2 Sheets) 6.2.1.2-26 MFWLB Subcompartment Analysis (2 sheets) 6.2.1.2-27 Calculated Pressures Regenerative Heat Exchanger Subcompartment 6.2.1.2-28 Calculated Pressures Radioactive Pipe Chase Subcompartment 6.2.1.2-29 Calculated Pressures RHR 1A & 1B Valve Room Subcompartment 6.2.1.2-30 Steam Generator Loop Compartment Force and Moment Coordinate System 6.2.1.5-1 STPEGS Large Break LOCA Analysis, DECLG C D=0.8, SI, High T AVG, Containment Backpressure 6.2.1.5-2 Containment Fan Cooler Performance Curves

STPEGS UFSAR LIST OF FIGURES (Continued

)

CHAPTER 6 Figure Reference Number Title Number TC 6-12 Revision 1 8 6.2.1.5-3 STPEGS Large Break LOCA Analysis, DECLG C D=0.8, Min SI, High T AVG , Containment Heat Transfer Coefficient 6.2.2-1 P&ID Containment Spray System 5N10-9-F-05037#1 5N10-9-F-05037#2 6.2.2-3 Composite Piping, Reactor Containment Building - Plan - El. 83'-0" - Area 12 (Sheet 1 of 4) 5C15-9-P-05025-6 Plan - El. 83'-0" - Area 13 (Sheet 2 of 4) 5C15-9-P-05026-5 Plan - El. 83'-0" - Area 14 (Sheet 3 of 4) 5C15-9-P-05027-5 Plan - El. 83'-0" - Area 15 (Sheet 4 of 4) 5C15-9-P-05028-6 6.2.2-4 P&ID HVAC Reactor Containment 5V14-9-V-00016#1 Building, Fan Coolers Subsystem 5V14-9-V-00016#2 6.2.2-6 Reactor Containment Building CSS Spray Coverage Plan

- El. (-)11'-3" 6C18-9-N-05001-2* 6.2.2-7 Reactor Containment Building CSS Spray Coverage Plan

- El. (-)2'-0" 6C18-9-N-05002-2* 6.2.2-8 Reactor Containment Building CSS Spray Coverage Plan

- El. 19'-0" 6C18-9-N-05003-2* 6.2.2-9 Reactor Containment Building CSS Spray Coverage Plan

- El. 37'-3" 6C18-9-N-05004-2* 6.2.2-10 Reactor Containment Building CSS Spray Coverage Plan

- El. 52'-0" 6C18-9-N-05005-1*

STPEGS UFSAR LIST OF FIGURES (Continued

)

CHAPTER 6 Figure Reference Number Title Number TC 6-13 Revision 1 8 6.2.2-11 Reactor Containment Building CSS Spray Coverage Plan

- El. 68'-0" 6C18-9-N-05006-2* 6.2.2-12 Reactor Containment Building CSS Spray Coverage Section B

-B 6C18-9-N-05007-1* 6.2.2-13 HVAC Reactor Containment Building Plan El. (-)11'-3" Area 13 5V14-9-V-00083 6.2.2-14 HVAC Reactor Containment Building Enlarged Plant and Section RCFC 5V14-9-V-00090 6.2.4-1 Containment Penetrations (100 Sheets) 6.2.4-2 Arrangement of Sump Piping 6.2.6-1 P&ID Containment Leak Rate Test 5C56-0-F-05058 (CLRT) Pressurization System 6.3-1 P&ID Safety Injection System 5N12-9-F-05013#1 5N12-9-F-05013#2 6.3-2 P&ID Safety Injection System 5N12-9-F-05014#1 5N12-9-F-05014#2 6.3-3 P&ID Safety Injection System 5N12-9-F-05015#1 5N12-9-F-05015#2 6.3-4 P&ID Safety Injection System 5N12-9-F-05016#1 5N 12-9-F-05016#2 6.3-5 Emergency Core Cooling System, Process Flow Diagram 6.3-6 Low Head SI Pump Performance Curves 6.3-7 High Head SI Pump Performance Curve

STPEGS UFSAR LIST OF FIGURES (Continued

)

CHAPTER 6 Figure Reference Number Title Number TC 6-14 Revision 1 8 6.3-8 RWST Level Setpoints 6.4-1 Control Room Envelope 6.4-2 Control Room Layout 6.5-1 Containment Sump pH vs. Time 6.5-2 Drop Size Distribution for the Sprayed Region

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